ML19253A961
| ML19253A961 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/10/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19253A953 | List: |
| References | |
| EOP-9, NUDOCS 7909130439 | |
| Download: ML19253A961 (34) | |
Text
CHANGE STdTION PROCEDURE CHANGE REQUEST
, gS' 79-2(2-17-51-2-A Procedure 6.7 tent changes require Station Review before using.
Procedure charaes witn prior Station Review do not need SRO approval.
EM NUMBER PROCEDURE TITLE Request Change
'TEMPOR ARY UNTIL :
PERMANENT CHANGE YES DATE NEEDED OR C NO l PERMANENs idSUED
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&&f& Y2f/b7 TIEOUESTOR WDATE ORIGINATOR:
Perform safety enaiysis on reverse for permanent.cnanges SHIFT ENGINEER: issue and tog cnange request. oistribu t e pink cop,es as sabeied.
send green copy to Station R e v ie w, remove empired t emporar y changes f rom books and discard, lif there is not a copy of the procedure in the labeled loc ation s distribute pink copies as needed.1 pf 2
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n TWO INDIVIOUALS hot. DING SENIOR REACTOR OPERATOR LICENSES
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FORM 17-51 A: PROCEDURE GROUP 1 7 909130 t/39 '
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Is a change to the Technical Specifications needed?
Yes No V Is the probability of an occurrence or the consequence of an accident or calfunction of equipment important to safety as previously evaluated in the SAR increased?
Yes N o ><
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Yes No x Because:
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CHANGE t uSRS' 71-2 9 4
STATlON PROCEDURE CHANGE REQUEST j
17-51-2-A R e vie ve before using.
Proceduce Intent ch.inges require Station Station Revievv do not need SRO approval.
Procedwie changes with preer bM 'T SP44 6/' SFA6 7c4 (! C o u f r',~
NUMBER PROCEDURE TITLE PERM ANENT Request Change
'TEMPOR ARY UN TIL :
CHANGE YES NEEDED DATE C NO OR PERMANENT ISSUED 04MX l>h 3 S /,3 W t hyg ht,4,~~c~
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Reason for change SkbYE $/ dNS
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REQUESTOR & DATE ORIGIN ATOR:
portorm sareiy anaiysis on reverse ter permanen t.cn.nge, SHIFT ENGINEER: issue and tog enange reauest. Distribu t e pink copies as iadeied.
Send green copy to St a tion R e v ie w, remove empired t emporar y changes f rom books and de scJ rd.
ilt there is not a copy vi the crocedure in the Wu}e pi n k copies a s needed.l labeled locat' s
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LIC E N S E S ghwo INDIVIDUALS HOLDING SENIOR RE ACTOR OPERATOR FORM 17-51 A: PROCEDURE GROUP 1 O( C'ON n0 -
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Is the probability of an occurrence or the consequence of an accident or to safety as previously evaluated in malfunction of equipment important the SAR increased?
Yes
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Is the possibility for an accident or malfunction of a differer.t type Yes
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than any previously evaluated in the SAR created?
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8 JUL34a79 5.0 IMMIDIATE /CTIO:;S 5.1 verify reactor trip and turbine trip 5.1.1 All rcds fully inserted.
5.1.2 All turbine stop & governor valves closed.
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"' # S 5.1.3 Trip ECP's if N ICA A "ZE A'C ' l'RE: Cud'ZS A LC"CL TA!!dCa ?'N A.,
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5.2 Verify safety injection actuation 5.2.1 Appropriate cccpenents have started and are operating properly.
5.2.2 observe monitor lights for equipmnt failures and proper equipmnt align:: rant. Take appropriate action for any malfunctioning equipment.
Group A - At paier lineup
~
Group B - Cold leg recirc. actuatien Group C - Containment spray actuation Group D - Safety injectica actuation gi g
J Group E - Phase A containment isolatica actuation 9
R%^Q Group F - Phase A contain:nent isolation actuation I
J U
Group G - Hot leg recirc. actuation db.
5.2.3 If Phase B - ccntain:nent isolation actuates, verify autcmatic acticns and dispatch cperator to open IVSN valve, per appendix H of this prccedurs'.
5.3 Monitor Tavg, pressurizer pressure and level, containment pressure, te:rperature and humidity for trends indicr. ting the severity of the accident.
Verify generator trip approximately 50 secondc af ter turbine 5.4 trip.
5.4.1 Generator breakers cpen.
(
Main feedwater and heater drain pumps trip.
5.4.2 5.5 Announce casually as soon as prsible.
93fi210 4
t
WP-9 PeV. ? 3 JU' " S.q 5.0 IMMEDIA'IE /CPIOtG 5.1 Verify reactor trip and turbine trip 5.1.1 All rods fully incerted.
5.1.2 All turbine stop & governor valves closed.
,e NN 6
5.1.3 TrgnCP's if pr::r. level is_loct.
Initiate natural cirEufation as per EDF7, App. A as 5d49 socn as possible.
l' 0
qs AS M%% G. O 5.2 Verify safety injection actuatico 54p G. 3 5.2.1 Appropriate ccrpenents have started and are operating properly.
5.2.2 Observe monitor lights for equigtent failures and proper equiprent aligr. ent.- Ta<e appropriate action for any mlfunc~icning equipment.
Group A - At pcwer lineup Group B - Cold leg recirc. actuation
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D Group C - Ccntainment spray actuatica CO Group D - Safety injecticn actuatica OM~%~}
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Group E - Phase A centainment isolaticn actuation Group F - Phase A cuitainment isolaticn actuation Group G - Hot leg recirc. actuation 5.2.3 If Phase B - ccntainment isolatico actuates, verify autcmatic acticos and dispatch ocerator to cpen IVSW valve, per appendix H of this procedure.
5.3 Monitor Tavg, pressurizer pressure and level, contain ent pressure, termerature and numidity for trends indicating the severity of the accident.
5.4 verify generater trip approximately 50 seconds after turbire trip.
5.4.1 Gebratcr breakers open.
5.4.2 Main feedsater and heater drain pu ps trip.
5.5 Announce casualty as socn as possible.
4
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., m-IUt' 9 Ri 'v. d ~5 t>. 0 RilkSiUC.T / CIONS 6.l iht rectivery t ro.a a falm or trudvet tent. J i!cty inj. ct u'n, proceed accor< ling to Atp niiix C of thin pn cedure.
Pol h.< tn.
subsequent actionr. ot II;P-L to insure prip'r nmen<1ary plant lineup.
6.2 Initiate emergency plan [>r E.P.I.P.
tmE Steam Generator Invel indi(:ation will te af fected L;y containment te:ri>erature.
Refer to at'pendix I, Steam Cer et atot Invel Correction Factors, to determino a noro accurate level.
t!]LL:
%g At first indicacten on S/G narrcu ranqe level indicater emuco aux. feecwater tlw to 50 GIM to preclude an inadverter.t itet/
D injectico due to. iter ha.m
't.
Aux. fe iw iter t ir a my : -
increased at ti.e utscretirn of the Shif t Sorervinor.
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6.3 Establish 50 to 150 G M auxiliar / teeuw. iter iLw p'r :.t.u:"
generator and maintain prograrmi level when.leveln have Ncn twovered.
6.3.1 If time permits, crxr ence coolchwa using stean ou:rp system or atrorpneric rehef valves to cool stenra generatorn.
6.4 Align control btard saitenes per Appendix A of t
"w.
6.5 Instruct plant cperators to 1.xostigate elui ment not t
functioning pro:nri/ an indicated t;y the control trard statns 1ights.
6.6 Cold I q Injoction 6.0.1 h%n cont.rol tmrd ali'jn:::ent rua t.een cwpleted reuet safety injectinn.
6.6.2 hhen the spray ackiitive tan 4 indicatec empty:
i A.
Push toth "containa'nt spray phase "B" innlation recet" punnbutton~.
t B.
Cloce cpray addi tive valvec bOV-CS-0008, M11-CS-0009 and :U/-C3-0010.
C.
Stop all cpray pu.Tpc, except i mtor driven (A er l
B).
}
6.6.3 hhen !M.ii-Level reacheu the low level alarm (13'-7",
at ip rox. l
- 7,000 'i. d. ), pticeed to cold leg recirculation as ;er Section 6.7 (Tm !diR pu:.Tn operal>le) or 6.J (Cne iUT pttri) int >t.;rab le).
336212 s
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EDP-9 LOSS OF REACIOR COOLANT TABLE OF CONTC.TS O
SELTION TITLE PAGE DATE REV.
5 Table of Contents 1
E6n 1.0 Purpose 2
8-10-77 1
2.0 References 2
8-10-77 1
3.0 Symptms 2
8-10-77 1
4.0 Autmatic Acticns 3
7-5-79 2
5.0 Imediate Actions 4
7-31-79 2
8 6 '"
2 6.0 Subsequent Actions 5
6 7-5-79 4
7 4-11-78 4
8 4-11-78 3
9 4-11-78 3
10 7-5-79 2
11 8-10-77 1
12 8-10 1 Appendix A SI Valve Positions 13 8-10-77 1
Appendix B SVAG 14 4-11-78 3
Appendix C Recovery Fran a False 15 8-10-77 1
or Inadvertent SI.
16 8-10-77 1
17 8-10-77 1
Appendix D B.I.T. Flushing 18 8-10-77 1
Appendix E Restoring B.I.T.
19 8-10-77 1
Concentration.
AEpendix F Containment Post SI 20 8-10-77 1
Inspecticn 21 8-10-77 1
Appendix G !ICS Valve 22 8-10-77 1
Interlocks 23 8-10-77 1
Appendix H IW Valves 24 8-10-77 0
Appendix I Steam Generator Level Correction Factors 25
- 6 '"
0 NIA2IO ATM g
W is procedure contains 25 pages.
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EDP-9 Rev. 1 8-10-77 ZION STATION EMERGDJCY CPERATING PROCEDURE EDP-9 IOSS OF RE/CICR COOIMI' l.0 EURICSE This procedure outlines the required actions in the event of a break in the primary pressure boundary exceeding maximum charging capacity.
2.0 REFERE;CES 2.1 Zion Technical Specifications 2.2 Zion Emergency Plan, E.P.I.P.
2.3 Zion Operating Instruction, SOI-4 2.4 Zion Cperating Instruction, SOI-5 0
2.5 Zion Operating Instruction, SoI-9 2.6 Zion Cperating Instruction, SOI-ll 3.0 SYMPICris 3.1 High radiation levels in ccntainment:
3.1.1 PO-2 ccntainment area - 560' level 3.1.2 PO-7 incore seal table area 3.1.3 RT-AR01 containment area - 617' level 3.1.4 R-ll, containment atz sphere 3.1.5 R-12, ccntainment at:nocphere 3.2 Containment humidity, pressure, and/cr te::perature indicating high.
3.3 Pressurizer pressure / level lcw and decreasing.
3.4 Pressurizer safety injection press / level low reactor trip.
936214 2
EDP-9 Rev. 2 JUL 5 79 4.0 AUIOMATIC /CTICNS O
4.1 Charging floa will increase attempting to maintain pressurizer level 4.1.1 Autmatic make-up attempts to maintain V.C.T. Level.
4.1.2 Charging pump sucticn shifts to R.W.S.T. on low-low level in V.C.T.
4.2 Letdown isolates and pressurizer heaters deenergize on low pressurizer level.
4.3 Reactor / turbine trip on low pressurizer pressure.
4.3.1 Steam dumps may actuate.
4.3.2 Atmocpheric relief valves may actuate.
4.3.3 Feedwater isolation with lo.* Tavg.
4.3.4 Generator trip approximately 50 seconds af ter turbine trip.
1.
Main feedvater pumps trip 2.
Heater drain pt=ps trip O
4.4 Safety injecticn actuation on low pressurizer pressure.
4.4.1 Auto start 1.
Charging pu ps A and 3 2.
Safety injection pt=ps A and B 3.
Residual heat removal pt=ps A and B 4.
Diesel generators 0, A, and B 5.
Service water pumps A, B, and C 6.
Component cooling puts A, B, and C (C,D, and E) 7.
1,uxiliary f cedwater pt=ps A, B, and C 4.4.2 Containment fan coolers shift to slow speed with dampers in accident Itode.
4.5 Containment isolaticn - phase A 4.6 Containment isloation - phase 3 (If containment pressure is greater than 23 psig) 4.6.1 Centainment spray pumps A, B, and C autostart 4.7 Accumulators autmatically inject; if RCS pressure falls below 2 600 psig.
936215 3
IDP-9 8
Rev. 2 JUL 3 f 1979 5.0 IMMEDIA'IE ACTIONS 5.1 Verify reactor trip and turbine trip 5.1.1 All rods fully inserted.
5.1.2 All turbine stop & governor valves closed.
/
5.1.3 Trip PCP's if przr. level is lost.
Initiate natural circulation as per EDP-7, App. A as socn as possible.
5.2 Verify safety injecticn actuation 5.2.1 Appropriate components have started and are operating properly.
5.2.2 Observe mcnitor lights for equipment failures and proper equignent aligr nent. Taxe appropriate action for any malfuncticning equipment.
Group A - At power lineup Group B - Cold lag recirc. actuation Group C - Ccntainment spray actuation Group D - Safety injectico actuatico Croup E - Phase A containment isolatica actuation Group F - Phase A containment isolation actuation Group G - Hot leg recire. actuation 5.2.3 If Phase B - ccntainment isolation actuates, verify autcrnatic actions and dispatch cperator to open IVSW valve, per appendix H of this procedure.
5.3 Mmitor Tavg, pressurizer pressure and level, ccotainment pressure, te@;rature and humidity for trends indicating the severity of the accident.
5.4 Verify generator trip amroximately 50 seconds af ter turbine trip.
O 5.4.1 Generatcr breakers cpen.
5.4.2 Main feedwater and heater drain pumps trip.
5.5 Announce casualty as scco as possible.
936216 4
EDP-9 Rev. 2 NJG 6 79 6.0 SUBSELUENT /CTIONS 6.1 For recovery from a false or inadvertent safety injection, O
proceed according to Appendix C of this procedure. Follow the subsequent actions of EDP-1 to insure proper secondary plant lineup.
6.2 Initiate emergency plan per E.P.I.P.
M l
Steam Generator Invel indication will be affected by containment temperature. F.efer to appendix I, Steam Generator Invel Correction Factors, to determine a trore recurate level.
BOTE At first indication on S/G narrow range level indicatur reduce aux. feedwater flow to 50 GPM to preclude an inadvertent safety injection due to water har:ner. Aux. feedwater flow tray be increased at the discretion of the Shif t Supervisor.
6.3 Establish 50 to 150 G M auxiliary feedwater flow per steam generator and maintain prograrred level wnen. levels have been recovered.
6.3.1 If time permits, ccmence cooldown using steam du:g system or atmospheric relief valves to cool steam generators.
O 6.4 Align control board switches per Appendix A of this procedure.
6.5 Instruct plant cperators to investigate equignent not functioning properly as indicated by the control board status lights.
6.6 Cold Leg Injection 6.6.1 When control board alignment has been ccxr.pleted reset safety injection.
6.6.2 When the spray additive tank indicates empty:
A.
Push toth " containment spray phase "B" isolation reset" pushbuttons.
B.
Close spray additive valves MOV-CS-0008,
>W-CS-0009 and EV-CS-0010.
C.
Stop all spray pumps, except 1 motor driven (A or B).
6.6.3 When FWST level reaches the low level alarm (13'-7",
approx.147,0C0 Gal.), pecceed to cold leg O
recirculation as per Section 6.7 ("No PJm pumps operable) or 6.3 (Cne Edm pump inoperable).
5 38b21.7
_ _ _ _ _ - ~ _, _. _ _. - - - _ _
EDP-9 Rev. 4 TJL $ 77 6.7 Cold Ino Recirculation with 2 Plm Pumps Ooerable If steps 6.7.1 A through L are not completed prior to reaching TOTE:
i Stop all puxps the Iow-Iow level alarm (9'-10") on the R-lST.
f taking suction frcra the RiST; except the containment spray I
pumps if the spray additive tanx is not empty.
If EDCS valves fail to. stroke to the positicn ordered, ensure POTE:
valve is energized (SVAG) and refer to Appendix "G" for a list of inter 1ccks whien must ce satisfied for certain valves to furction.
6.7.1 Khen Msr reaches Iow level (13'-7") alarm A.
Stop par Purp B 1.
Open 50V-CC-34128 (CC frcxn PER heat exch.)
2.
Close 50V-RH-87003 (RHR pump B suction) 3.
Open F0V-SI-adlla. (recirc. su:tp suction)
Close F0V-RH-8716A and B (crosstie isolation) 4.
in the Verify greater than 111" (3 sets of lights lit)
B.
recirculation surp.
C.
Start RHR pump B.
O*
Verify cold leg injection flow on FI970A and FI970B.
D.
If safety injection pump ficw indicators FI-922 and 932 IDTE:
indicate little or no ficw, Step "F" must be accettplished i:=ediately af ter Step "E" is completed, to prevent damage to S.I. pump seals frca overheating.
Close SOV-SI8814 (SI pu.p miniflow valve) if valve does E.
not close, isolate :DV-SIB 813.
Open FCV-SI8804B (crosstie isolation valve).
F.
Verify PER Pu.p B is supplying the SI Pu'.ps by G.
increased SI Purp disch. press. (PI-923 & 935) and ficw (FI-922 & 932).
O sms 6
EDP-9 Rev. 3 4-11-78 H.
Stop RHR pump A.
1.
Open F0V-C9412A (CC from RER heat exch.)
2.
Close F0V-RH8700A (RHR pump A suction valve) 3.
Open F0V-SI8811A (recirc. sump isolation valve).
I.
Start RHR Pump A.
J.
Open FCV-SI8804A to align RHR to charging pump suction.
K.
Verify that RHR pump A is supplying the centrifugal charging pumps by increased disch. press (PI-947) and flow (FI-934).
L.
Close F0V-NC112D and F0V-NC112E (RhTF suction isolation valves).
6.7.2 If containment spray actuated.
A.
hhen spray additive tank indicates e.wty, Reset Phase "B" isolation by depressing botn " Cont. Spray.
Phase "B" Isolation Reset" pushbuttons.
B.
Close F0V-CS0008, 0009 and 0010 (Spray additive tank outlet).
C.
Stop A and C containment spray pumps.
D.
Close MJV-CS0002 and F0V-CS0006 (Disch. Stop valves).
E.
hten R.W.S.T. has been ccupletely emptied, stcp "B" containment spray pump, and 1.
Close F0V-CS0004 (disch. step valve).
2.
Have operator energi::e creaker for F0V-SIB 809A at FCC 1393A (23938) 560' A.B.
3.
Close F0V-SIS 809A ("A" RHR to cold leg inj.)
4.
Open F0V-CS0049 (RHR to cont. spray)
NOTE:
Containment spray flow should be '.naintained for minimum of two (2) hours af ter initiation.
F.
hhen containment pressure begins to decrease and_
containment spray flow has been maintained for a mini:r.um of two (2) hccrs.
O 336219 7
EDP-9 Rev. 3 4-11-78 1.
Close F0V-CS-0049 ("A" RHR to cont. spray).
2.
Open S W -SI6809A (MIR to cold leg inj.).
G.
Proceed to Step 6.9.
6.8 Cold leo recirculation with 1 RHR ourp inocerable.
NCTTE:
If Steps 6.8.1 A through J are not corpleted prior to reaching the low-lcw Invel alarm (9'J 0") on the RWST, stop all pumps taking sucticn fran the M:ST, except the containment spray pumps if the spray additive tans is not empty.
BME:
If EECS valves f ail to stroke to the pcsition ordered, ensure valve is energized (SV;6) and refer to Appendix G for a list of interlocks which must be satisfied for certain valves to function.
6.8.1 When R.W.S.T. level reaches the loa level alarm (13'-7") stcp the running miR purp and align as folioss:
A.
"A" RER pump operable.
1.
Open t0V-CC 9412A (CC fran "A" RHR heat exch.)
2.
Close FOV-RH8700A (RHR ptmp A sucticn) 0 3.
Open 50V-SI8811A (recire. simp isolation valve)
B.
Open 3DV-CC9412B (C frat "B" RHR Heat Exch.)
2.
Close dCV-mi87003 (RHR purp B suction) 3.
Open 50V-SI8811B (recire. st.p isolation valve)
C.
Verify greater than 111" (3 sets of lights lit) in the recirc. sump.
D.
Close SOV-Mi8716A and 20V-RH8716B (crosstie isolation valves).
O 0
8
EDP-9 Rev. 3 4-11-78
- h..
Start the operable R!!R PL":p.
O F.
Verify cold leg injection fl w by monitoring flow indicators FI-970A & B or FI-971 A & B.
G.
Open F0V-SI8807A and SCV-SI8807B (centifugal charging pump / safety injection pump suction crosstie valves).
tCIE:
If safety injection pump flow indications FI-922 and 932 indicate little or no flow, Step H.2 or I.2, as appropriate must be accmolished immediately af ter step H.1 or I.1 is ccmpleted, to prevent damage to SI pump seals frcxn overheating.
H.
If "A" RHR pump is ruraing 1.
Close bOV-SI8814 (S.I. pu.p mini flow) if valve fails to cicse, isolate TOV-SI8813.
2.
Open FDV-SI8804A ("A" FRR to chg. pump suction)
I.
If "B" RHR pump is running 1.
Close FOV-SIB 814 (SI pump miniflow).
If O
valve fails to close, isolate MOV-SI8813.
2.
Open bOV-SI8804B ("B" RHR to SI PL":p Suction).
J.
Verify operable RHR pump is supplying centrifugal charging pumps ano safety injection pumps oy increased discharge pressure and flw s (PI-947, 923 & 935, FI-934, 922 & 932).
1.
Close FEV-W112D and :CV-Wil2E (chg. pu:n EST suction).
6.8.2 If containment spray actuated A.
hten spray additive tank indicates empty, Reset Phase "B" Isolation by depressing both " Cont.
Spray / Phase B Isol. Rese;" pushouttons.
O 3364'21 9
w DOP-9 Rev. 2 M. 5 79 B.
Close FOV-CS0008, 0009 and 0010 (Spray additive tank outlet).
I C.
Stop A and C containment spray purrps.
D.
Close FOV-CS0002 and oOV-CS0006 disch. stcp valves E.
When R.W.S.T. has been errpletely emptied, stop "B" containmnt spray punp and close BOV-CS0004 (discharge stcp valve).
m:
With cnly one RHR pump operable, containment spray will not be supplied frcm the BHR system.
F.
If the second RER pump be unes cperable, refer to Section 6.7 of this procedure for prcper valve lineup.
6.9 If pressur; :er level begins to increase, control level and pressure by stepping charging pumps and safety injection pug s as necessary.
A.
Insure pressurizer heaters are off.
B.
If pressurizer goes solid, maintiain PCS pressure by stopping additional purps.
CAIJrION:
Prior to turning off any charging or safety O
injection p=ps, eneck all hot and cold leg tenperatures and ill core exit thermccouple temperatures against steam table saturation tenperatures to ensure subcooling in the core.
N7FE:
RHR Pumps shculd remain in operation for decay Heat Removal.
6.10 Simultaneous het and cold lea recirculation, with tw RHR punps operacle.
NOTE:
Hot and cold leg recirculation lineup my vary depending on the numoer of TCS pumps running.
If charging pumps are running, they should rerain on cold leg injection along with one RER pump.
6.10.1 When 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> have elapsed since safety injection actuation, realign the RHR system as follcws:
A.
Instruct operator to energize breaker for FOV-SId809B at 5001383A (2383B).
B.
Close SOV-SI8809B ("B" BHR to cold leg inj.)
C.
Instruct operator to energize breaker f c O
FOV-RH9000 at SCC 1383B (2382D) Soo'AB.
D.
Open MOV-RH9000 (RHR to hot leg inj.).
036222 10
EDP-9 Rev. 1 8-10-77 E.
Open FOV-RH87168 (ME crosstie 1s01.).
F.
Verify M E hot leg injection flow on FI-600.
lOIE:
If no flow is indicated af ter Step F. verify MOV-RH8703 is open.
6.10.2 Realign safety injection system to hot leg recirculation as follows:
A.
Stop "A" safety injection p=p if not stopped for pressure control.
B.
Close >W-SI9010A ("A" S.I. to cold leg inj.).
C.
Instruct operator to energi::e breaker for FW-SI90llA at SCC 1372 (2372) 542' A.B.
D.
Open 50V-SI90llA ("A" SI to hot leg inj.).
E.
Start "A" safety injegtion pu::p and verify flow on FI-922.
F.
Stop "B" safety injection pLg..
G.
Close FOV-SI90108 ("B" S.I. to cold leg inj.).
H.
Instruct operator to energize breaker for O
FOV-SI90llB at MCC 13838 (23638) 560' AB.
I.
Open MOV-SI90llB ("B" SI to hot leg inj.).
J.
Start "B" safety injection pu::p and verify flow on FI-932.
6.11
_ Simultaneous hot and cold leo recirculation with one RHR p rp inoperacle.
6.11.1 When 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> have elapsed since safety injection actuation, realign the one cp2rable MIR system as follows:
A.
Instruct coerator to energize breaker for bOV-Si8809A at FCC 1393B (23938) 560' AB.
B.
Close 50V-SI8809A ("A" MB to cold leg inj.).
C.
Instruct ooerator to energize breaker for F0V-SI88098 at FCC 1383A (2383B) 560' AB.
O 11
EDP-9 Rev. 1 3-10-77 D.
Close FW-SI88098 ("B" RHR to cold leg inj.).
O E.
Instruct operator to energize breaker for FM-RH9000 at FCC 1383B (2383B) 560' AB.
F.
Open FM-RH9000 (RHR to hot leg inj.).
G.
Open bW-RH8716A (If "A" pump operable) or MOV-Pli8716B (If "B" pump operable).
i!.
Verify PJm to hot leg injection flw on FI-600.
TOTE:
If no flw is indicated after Step H. verify FM-RH8703 is open.
I.
Insure adecuare suctico head to safety injection pumps.
6.11.2 Realign safety injection to hot leg recirculation as follms:
tore:
Safety injection perps should only be realigned to hot leg recirculaticn if the charging pumps are cperating cn cold leg injection, as tne other RHR train is inoperable.
A.
Stop "A" safety injection pump.
B.
Close F W -SI9010A ("A" SI to cold leg inj.).
C.
Instruct operator to energize breaker for F M -SI9011A at MCC 1372 (2372) 542' AB.
D.
Open b W -SI90llA ("A" SI to hot leg inj.).
E.
Start "A" safety injection pump and verify SI flw to hot leg inj. cn FI-922.
F.
Stop "B" safety injectica pump.
G.
Close FIN-SI9010B ("B" SI to cold leg inj.).
H.
Instruct operator to energize breaker for FW-SI90llB at bCC 1383B (2383B) 560' AB.
I.
Open dW-SI90llB ("B" SI to hot leg inj.).
J.
Start "B" safety injection pump and verify flw cn FI-932.
O 2
33ti224
=_
EDP-9 Rev. 1 8-10-77 EOP-9 APPE; DIX A SAFEIY ItGECTION VALVE POSITIONS i
1.
Control board front A,
Closed ICV-E'510 ICV-nl530 ICV-EW510A ICV-Bi530A IrV-bis 20 ICV-bis 40 IfV-EW520A IfV-B1540A C.W-BD0001 OAV-BD0005 OAV-BD0002 OAV-BD0006 CAV-BD0003 CAV-BD0007 CAV-BD0004 CAV-BD0008 2.
Control board back A.
Closed OAV-DT3157 OAV-I7r9170 OAV-I7r915?A and B Irv-I7r1003 OAV-DT9160A and B ECV-WD17 A and B ECV-BD17 EU/-IA01A and B ECV-RVlli ECV-RV0001 FCV-RV112 ECV-RV0002 FCV-RVll3 FCV-RV0003 ECV-RVll4 ECV-RJ0004 FCV-SSO4 FCV-SS02 ECV-SS05 ECV-SS03 B.
Open EU/-EiO8 ECV-IW13 FC/-IWO9 ECV-D114 FCV-Ei10 EC/-Eil5 FCV-IWil FCV-IW16 FCV-IW12 EEV-Eil7 3.
See Appendix C, section 1.13 for cont. isol. valves, page 15 and 16 of this peccedure, for valves to be realigned refore resetting S.I. signal.
D362:35 13
~ - - - - - - -----
E P-9 Rev. 3 4-11-78 E0P-9 APPHOIX B SPURIOUS VALVE ICIUATION GROUP tOIE: 'mese valves are to be energize ' on an as needed basis to ensure no spurious actitation valve repositioning during the S.I.
1.0 30 minute group (redi A.
!OV-SI8809A (1393B, 2393B) 2.0 19 hour2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> group ' yellow)
A.
FM-SI9011A (1372, 2372)
B.
FM-SI90llB (1383B, 2383A)
C.
F W -BH9000 (1383B, 2383B)
D.
FM-SI8809B" (1383A, 2333B)
~
O 3.0 tkn-energized group (green)
A.
F M-RH8703 (1381B, 2381B)
B.
F M-SI8802 (1383A, 2383B)
C.
MOV-SI8806 (1383A, 2383A)
D.
MOV-SIB 812A (1393A, 2393B)
E.
F W -SI8812B (1393A, 2393B)
F.
FW-SI8808A (1371, 2371)
G.
FW-SI88088 (1381B, 2381B)
H.
FM-SI8808C (1391, 2391)
I.
MOV-SI8808D (1371,2371)
O omau 14
_ _ =
W P-9 Rev. 1 8-10-77 EDP-9 APPENDIX C RTOVERY FEnt A FALSE CR INADVERTENT SAITIY INJETION 1.0 Recovery Actions 1.1 Reset safety injection.
1.2 Stop B.I.T. injection flow.
1.
Open charging purp miniflow isolation valves (FOV-W8110 and 8111) 2.
Close B.I.T. inlet valves (bOV-SI8803A and 3).
3.
Close B.I.T. outlet valves (50V-SI8801A and B).
4.
Stop one centrifugal charging pur:p.
1.3 Return charging system to normal.
1.
Open V.C.T. outlet valves (b0V-Wil23 and C).
2.
Close CVCS suction from RNST (MOV-Wil2D and E).
3.
Open charging header isolation valves.
(bOV-VC8105 and 8106) 4.
Open reactor coolant pt.=p seal return valve.
(MOV-VC8100)
O 1.4 Restore nceral letacwn.
1.
Open letdoan containment isolation valves.
(AOV-W8152 and 8153) 2.
Open letdown isolatien valves (LCV-VC459 and 460).
3.
Open PCV-131 in ranual centrol.
4.
Open 75 GE1 orifice block valve.
(OAV-W 8149B or C) 5.
Place PCV-131 in autcratic.
1.5 Open main steam isolation valves if closed.
1.
Verify steam dur:ps closed.
2.
Verfiy M.S.R. steam supply and purge valves closed.
3.
Verify S.J.A. ejectors off, aux. steam and turbine gland seals on aux. toiler er cpposite unit.
4.
Pressurize steam lines using ti.S.I.V. 'oypass valves per GOP-1, Section 3.7.
5.
hten steam line pressure is within 50 psig of steam generatcr pressure, open MSIV's.
O sm 15
DDP-9 Rev. 1 8-10-77 EDP-9 APPDOIX C (Continued) 1.6 Return safety injection pumps to standby.
1.7 Restore containment faa ccolers to normal operation.
1.
Reset containment ventilation isolation.
2.
Verify dampers reposition to normal.
3.
Start two or three cont. fan coolers in fast speed.
1.8 Auxiliary feedwater system.
1.
Stop one motor driven pump.
2.
Stop turbine driven pump, if operating.
3.
Establish 50 GEN feedflow to each steam generator.
1.9 Restore service water system to normal.
1.
Open turbine bldg. isolation valves.
(bOV-SN0100 and 0115) 2.
Open S.W. boost. pu:rp isol. valves.
(FDV-SN0005 and 0C06) 3.
Start S.W. boost. pumps.
4.
Place one service water pu p in standby.
O 5.
Place fire pmps in standby.
1.10 Place one wWent cooling purp in standby.
1.11 Return residual heat removal pumps in standby.
1.12 Return diesel generators to normal.
1.
Step "0" D.G.
2.
Stop "A" or "B" diesel generator.
3.
Reestablish safety shutdcwn to cperating diesel by depressing " safety shutdown reset" pushoutton on local D.G. panel.
1.13 Restore containment isolation valves to rcrmal.
1.
Open the follcwing valves en back of control board.
A.
ECV-SA01A and B (service air)
B.
FCV-VF01A and B (filtered vent header)
C.
PC-VN01A and B (stem. line icw pt. drain)
D.
FI-SS9354A and B (pr:r. stm. sample)
E.
EC/-SS9355A and B (pr:r. liquid sample) 0 16
LDP-9 Rev. 1 8-10-77 F.
ECV-SS9356A and B (hot leg sa:nple)
O G.
EUV-SS9357A and B (accum. samples H.
ECV-PR19A and B through 23A and B (Rx leak detect. )
2.
Open the following valves on the front of control board.
A.
ECV-PR24A and B (cont. air sarple)
B.
OAV-RC8028 and 8029 (P.W. to P.R.T.)
3.
Open the following valves at the waste gas panel.
A.
Dr9170 (BCDT pump disch. valve)
B.
Dr9160A and B (BCUP vent) 1.14 Refer to Appendix-D to flush B.I.T. injection lines to R.C.
loops.
1.15 Refer to Appendix-E to restore B.I.T. concentration.
1.16 Refer to lyp2ndix-F for post safety. injection containment inspection.
0 0
336229 17
EDP-9 Rev. 1 8-10-77 EDP-9 APPEDIX D FWSHItG B.I.T. I?UECTION LINE:S TO R.C. IDOPS 1.0 Procedure 1.1 Shif t frcxn positive displacement charging pump to centrifugal charging pu:1p, if applicable.
1.2 Close F0V SI-88005, C, and D.
1.3 Ibrottle open B.I.T. manual bypass valve (SI-8925)
CAUTION:
Maintain R.C. pump labyrintha P by adjusting HCV-182.
1.4 Verify flow on FI-924 or V.C.T. level decrease.
1.5 After 5 minutes, open SDV-SI8800B and close 30V-SI8800A.
1.6 Verify ficw on FI-925 or V.C.T. level decrease.
1.7 After 5 minutes, open BOV-SI8800C and close 3DV-SIS 800B.
- 1. 8 '
Verify floa on FI-926 or V.C.T. level decrease.
O 1.9 After 5 minutes, open SDV-SI8800D and close 50V-SI8800C 1.10 Verify flow on F::-927 or by V.C.T. level decrease.
1.11 After 5 minutes, close and lock SIB 925.
1.12 Open 50V-SIS 800A, B, and C and return charging pumps to rcrmal.
O 336230 18
E0P-9 Rev. 1 8-10-77 EDP-9 APPENDIX E RESTORItG BIT COBCHTTRATION A.
Preferred Method (Flush to II.U.T.)
1.
Line up standby B.A.T.
(normally 03) to supply affected units make up and B.I.T. ranual supply and return valves.
2.
Open SI-8913 (B.I.T. outlet to H.U.T.).
3.
Open A0V-SI8883 (B. A.T. pump to B.I.T. isol. valve).
4.
Shift appropriate B.A. transfer pump to fast speed.
5.
Verify ficw cn FI-949 (B.I.T. flow meter).
6.
Flush approximately 1000 gal. through the B.I.T. to the H.U.T.
7..
Shut SI-8913 (B.I.T. outlet to H.U.T.).
8.
Open ACV-SI-8807A & B (B.I.T. to B. A.T. iso'. valves).
9.
Verify flcw on FI-949 (B.I.T. flow meter) 10.
Recirc. for 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and verify concentration of B.A.T.
11.
If necessary batch a high concentration batch to bring B.A.T.
and B.I.T. into specs.
12.
Return affected unit's normal B.A.T. to supply makeup and B.I.T. recirc. supply and return.
B.
Alternate method (Recirc. and Batching) 1.
Line up standby B.A.T. (normally OB) to supply affected units make-up, and B.I.T. recirc supply and return manual valves.
2.
Open A0V SI-8883 (B. A.T. purp to B.I.T. Isol. valve) and AOV SI-8870A & B (B. I.T. to B.A.T. Isol. Valves).
3.
Shift appropriate B.A. transfer pu:p to fast speed.
4.
Verify flcw cn FI-949 (B.I.T. ficw meter).
5.
Recirc. B.I.T. for 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
6.
Pericdically sarple and batch high concentration batches to bring B.A.T. and B.I.T. into specs.
7.
Return affected units normal B.A.T. to supply make-up and O
B.I.T. recirc. supply and return.
33W231 19
EDP-9 Rev. 1 8-10-77 EDP-9 APPENDIX F COtfIAINMENT IOST SAFEIY ItCEI: TION INSPEX: TION
Purpose:
'Ib specify a visual inspection to be performed af ter any actuation of the safety injection systems. This inspection will satisfy the technical specificaticn requirement (3.3.2.F) for verifying integrity of the reactor coolant system.
Procedure:
Inspect the areas listed below for any signs of leakage, hydraulic snubber actuation, hanger deformation, structural deformation or any other visual indication of change:
AREA OF INSPIrrION
,INSPICIORS INITIALS 1.
Boron injection nozzles:
Icop A Icop B Icop C Icop D 2.
Mechanical pipe penetration Area (inside containment):
Upper IAvel Iower IAvel 3.
Reactor vessel head area (CRIN's &
conoseals) 4.
Reactor vessel cavity 5.
Reactor coolant loops (including PCP seal hangers, snubbers and valves):
Icop A Icop B Icep C Iccp D 6.
Pressurizer relief tank (including O
rupture discs)
- 7. Reactor coolant drain tank 2
936230
=_
=
WP-9 Rev. 1 8-10-77 mP-9 APPHOIX F (Continued) 8.
Accumulator A Accumulator B Accumulator C Accumulator D 9.
RCS instrumentation (walk down of all RCS instrument racks outside of the missile barriers).
Outside barrier upper level Outside barrier icwer level Inspected by SE/SF (SRO)
Date O
D36'233 21
.. =
EDP-9 I
Rev. 1 j
8-10-77 EDP-9 l
t APPENDIX G l
EDCS VALVE INTERIDCKS l
l RH8701 & RH8702 l
l RHR suction valves fran lcop "A" hot leg i
cannot be opened unless reactor coolant system pressure is equal i
to or less than 425 psig.
RH8700A RHR pump "A" individual suction valve can be cpened only if the following is satisfied:
CS0049 is closed CS0050 is closed SI-8804A is closed SI8811A is closed RHR pump "B" individual suction valve can be opened only if the follcw1..g is satisfied:
CS0049 is closed CS0050 is closed SI8804B is closed SI8811B is closed CS0049 RHR supply to containment spray header can be opened only if SI8811A is open CS0050 RHR supply to containment spray header can be cpened only if SI8811B is open i
SI8811A l
O Centainment sump suction valve can be cpened cnly if RH8700A is closed 22
EP-9 8
Rev. 1 8-10-77 EP-9 APPENDIX G (Continued)
SI8811B Containment sump suction valve can te opened only if RH87008 is closed SI8804A RHR supply to the centrifugal charging purp suction header can be opened only if the following is satisfied:
SI8811A is open and either RH8701 or RH8702 is closed or Control switch on safeguards test panel in test and either RH 8701 or RH 8702 is closed SI8804B RHR supply to the SI pump suction header can be opened only if the following is satisfied:
SI8813 ce SI8814 is closed (SI recire. to RXST) and either SI88113 O
open o_r cor trol switch on safeguard test pel is in test and r
either EH8'31 or RHS702 closed O
samas 23
WP-9 Rev. 0 8-10-77 mP-9 O
APPDOIX H IW SYSTD4 b'M;UAL VALVES UNIT 1 & 2 tDIE On actuation of Phase B containment isolation, these IW system manual valves must be repositioned to the open position in order to carplete ccntainment isolation.
IW-154; FCP seal water, 574' pipe chase IW-155; FCP seal water, 574' pipe chase IW-156; RCP seal water, 574' pipe chase IW-157; RCP seal water, 574' pipe chase IW ' 3; 122; CC to PCP's, 582' pipe chase IW-19e ; 199; CC from FCP's, 582' pipe chase Cr fran RCP's, 582' pipe chase O
IW-197; 120; IW-153; Charging header, 590' pipe chase O
samas 24
EOP-9 Rev. 0 APPENDIX I
/m 6 7*
Steam Generator Level Correction Factors 0
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Ap,511 cable to both Narrow and Wide Range Level Channels O
936237 25 FINAL